Preliminary Evaluation of PWR Safety & Relief Valve Test Program Results,Point Beach Nuclear Plant. One Oversize Drawing Encl.Aperture Card Is Available in PDRML20050D592 |
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Site: |
Point Beach ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
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Issue date: |
03/31/1982 |
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From: |
EDS NUCLEAR, INC. |
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To: |
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Shared Package |
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ML20050D577 |
List: |
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References |
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RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8204120346 |
Download: ML20050D592 (9) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20217J5801997-08-0505 August 1997 Revised Pages to CAA-96-146, Criticality Analysis of Point Beach Nuclear Plant Spent Fuel Storage Racks Considering Boraflex Gaps & Shrinkage W/Credit for Integral Fuel Burnable Absorbers ML20140D0481997-04-15015 April 1997 Suppl to Evaluation of EQ Impact of Wepc TS Change Request 192 ML20147J2821997-03-10010 March 1997 Rev 2 to Potential Failure of Redundant SR Circuits,Within Mcb ML20140G9941997-02-27027 February 1997 MR 96-069*A, Replace Breakers in 1Y-06, MR 96-069*B, Replace Breakers in 1Y-05 ML20140H0121996-11-15015 November 1996 MR 96-070, Replace Breakers on 2Y-05/06 ML20117L0141996-09-30030 September 1996 Evaluation of Possible Water-Hammer Loads in Svc Water Sys for DBA Conditions ML20117L0051996-09-0909 September 1996 Rev 0 to Operability Assessment for Transient Conditions in Pbnp Svc Water Sys During Coincidental LOCA & Loop,Safety Related ML20141G8411996-05-14014 May 1996 Criticality Analysis of Point Beach Nuclear Plant Spent Fuel Storage Racks Considering Boraflex Gaps & Shrinkage W/ Credit for Integral Fuel Burnable Absorbers ML20096H0181996-01-16016 January 1996 Rev 1 to Seismic Evaluation Rept ML20096H0221996-01-16016 January 1996 Rev 1 to Relay Evaluation Rept ML20094M9461995-11-14014 November 1995 Repair Roll Qualification ML20087H5701995-06-30030 June 1995 Rev 0 to Seismic Evaluation Rept ML20087J7251995-06-30030 June 1995 Rev 0 to Relay Evaluation Rept ML20086B4951995-06-0202 June 1995 Rev 0 to Point Beach Nuclear Plant Emergency Action Technical Basis Document ML20081G4681995-02-27027 February 1995 Rev 0 to Evaluation of Covered Cable Trays in AFW Pump Room at Point Beach Nuclear Plant,Fire Zone 304 ML20078S3621995-02-17017 February 1995 Unit 2 Refueling 20 Repair/Replacement Summary Rept for Form NIS-2 ML20057D9391993-09-21021 September 1993 Rev 0 to Pbnp Diesel Generator Addition Project Design Summary ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20086U1171992-01-0707 January 1992 Rev 0 to Eighteen-Yr Inservice Tendon Surveillance Test Rept,Units 1 & 2 Containment Bldg Post-Tensioning Sys ML20082D4651991-07-22022 July 1991 Wisconsin Electric Power Co Point Beach Nuclear Plant Simulator Certification Rept - Jul 1991 ML20081M7581991-06-27027 June 1991 Addendum to Annual Results & Data Rept for 1987,1988 & 1989 Point Beach Units 1 & 2 ML20247C5971989-04-30030 April 1989 Containment Liner Plate Leak Chase Channel Pressure Boundary at Point Beach Units 1 & 2 ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20195C3001988-10-31031 October 1988 Final Rept for Increased Peaking Factors & Fuel Upgrade Analysis ML20153G7751988-08-31031 August 1988 Safety Evaluation for Increased Peaking Factors & Fuel Upgrade at Point Beach Nuclear Plant Units 1 & 2 ML20154H2571988-04-25025 April 1988 Supplemental Analyses & Comments/Responses to Epri/Wog Analysis of Decay Heat Removal Risk at Point Beach ML20154H1511988-03-31031 March 1988 Difference Between Sandia & NUMARC Analysis of Decay Heat Removal Related Risk for Point Beach ML20154H1871988-03-30030 March 1988 Final Draft Supplemental Analyses & Comments/Responses to Epri/Wog Analysis of Decay Heat Removal Risk at Point Beach ML20148C9851988-02-29029 February 1988 Response to 10CFR50,App R 'Alternate Shutdown Capability,' 4,160 Volt Switchgear Room ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235J3751987-08-31031 August 1987 Rev 1 to Evaluation of Pressurizer Safety & Relief Valve Sys Final Rept ML20236D3901987-07-22022 July 1987 Summary Rept:Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Nuclear Plant Unit 1,1987 ML20236J7371987-07-0101 July 1987 Partially Withheld Final Rept of Ad Hoc Investigation Committee for 870619 Release. Related Info Encl ML20215B6761987-06-0202 June 1987 Evaluation & Analysis of Point Beach Nuclear Plant Unit 1, Reactor Vessel Safety Injection Nozzle-to-Shell Weld Indication ML20205P5461987-03-31031 March 1987 Crdr Summary Rept ML17347B6741987-02-11011 February 1987 Results of Boraflex Exam,Point Beach Nuclear Plant. ML20236N4481987-01-21021 January 1987 Rev 3 to Emergency Operating Procedures, Training Course Syllabus ML20204F1541986-06-30030 June 1986 Evaluation of Containment Liner Plate Leak Chase Channel Sys for Point Beach Nuclear Plant Units 1 & 2 ML20086U1111985-05-15015 May 1985 Containment Bldg Post-Tensioning Sys Thirteen-Yr Surveillance ML20115G3561985-04-30030 April 1985 Radwaste Cost-Benefit Analysis ML20087N4381984-03-30030 March 1984 Sizing of Ultrasonically Detected Indications in Point Beach,Unit 1 Reactor Pressure Vessel Outlet Nozzles ML20087N4431984-03-27027 March 1984 Reactor Vessel Outlet Nozzle-to-Shell Weld Flaw Indication Fracture Mechanics Evaluation for Point Beach Nuclear Plant, Unit 1 ML20087K2161984-03-0505 March 1984 Westinghouse Safety Evaluation,Cracked Control Rod Guide Tube Support Pins ML20107F2701984-01-31031 January 1984 Nonproprietary Software Design Rept for Class a Model & Meteorological,Radiological Effluent & Dose Repts for Point Beach Nuclear Plant ML20080K9511983-12-31031 December 1983 Criteria for Determining Duration of Integrated Leakage Rate Tests of Reactor Containments ML20081E5171983-10-31031 October 1983 Final Rept,Response to 10CFR50 App R `Alternate Shutdown Capability.' ML20077M4371983-08-31031 August 1983 Safety Evaluation for Point Beach Units 1 & 2 Transition to Westinghouse 14X14 Optimized Fuel Assemblies ML20072L9751983-06-0808 June 1983 Present Status & Projected Future Progression of Steam Generator Tube Corrosion/Degradation at Point Beach Unit 1, Wisconsin Electric Power Co,Two Creeks,Wi ML20072C4431983-03-0101 March 1983 Amend 1 to Steam Generator Repair Rept 1999-06-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
[Table view] |
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PRELIMINARY EVALUATION OF PWR SAFETY AND RELIEF VALVE TEST PROGRAM RESULTS POINT BEACH NUCLEAR _ PLANT Prepared for:
Wisconsin Electric Power Company March 1982 i
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l 8204120346 820408
) PDR ADOCK 05000266 P PDR L
WISCONSIN ET,ECTRIC PRET,IMINARY EVALUATION POINT BEACII NUCT. EAR PLANT Page 1 of 8
1.0 INTRODUCTION
This report summarizes the preliminary evaluation of the capability of the Point Beach Nuclear Pla n t (PBNP), Units 1 and 2, cafety and relief valves to operate under expected operating and accident conditions. This preliminary evaluation is based upon a review of the results obtained by the Generic PWR Safety and Relief Valve Test Program, implemented by the Electric Power Research Institute (EPRI) at the request of participating PWR Utilities.
2.0 SYSTEM DESCRIPTION PBNP consists of two nuclear steam supply systems and two turbine generators; i.e. it is a two-unit power plant. Each unit is a pressurized water reactor system with two primary coolant loops, supplied by Westinghouse Electric Corporation. Each NSSS is rated at 1518 MW thermal. In general, Unit 2 is a mirror image of Unit 1.
The safety and relief valve system for each unit consists of:
o Two spring-loaded, Crosby Valve and Gage Co.
IIB-BP-86 series safety valves o Two Copes-Vulcan Inc. power-operated relief valves o Two Velan gate-type block valves with Limitorque operators I
l o Three pressurizer outlet piping lines: one j line, including a loop seal, for each of the l
two safety valves, and one (branching) line l for the block and power-operated relief valves l
i o A common discharge piping line, terminating in I
the pressurizer relief tank
WISCONSIN ELECTRIC PRELIMINARY EVALUATION POINT BEACil NUCLEAR P L A N' '
Page 2 of 8 An isometric <irawing of the safety and relief valve system for PBNP U it 1 is attached hereto (EDS Nuclear Drawing No. PBNP-S RV-01) . This drawing represents the as-built Unit 1 piping, as confirmed by the Wisconsin Electric program for NRC IE Bulletin 79-14. ' 'h e Un i t 2 piping layout is essentially a mir:or image Jwith slightly different supports 2: a Unit 2 drawing is not attached hereto.
Detailed parameters for the valves and piping are given in Tables 1, 2, 3, and 4.
3.0 PRELIMINARY EVALUATION 3.1 Applicability of EPRI Test Data Safety Valves - PBNP has Crosby ifB-BP-86, 4 K2 6 safety valves with loop seal inlet piping configurations. The EPRI Test Program included Crosby 6M6 and 3K6 safety valves with loop seals.
The Crosby safety valve test results are contained in Sections 3.4 and 3.5 of the EPRI Safety And Relief Valve Test Report. The 6M6 and 3K6 valves l are structurally and functionally similar to the 4 K2 6, and their test results are applicable.
i l Relief Valves - PBNP has four (two per unit) l Copes-Vulcan relief valves. One of the PBNP valves is essentially identical to a valve included in the EPRI Test Program. The only difference between the i
- three remaining PBNP relief valves and the test valve is in the valve body size (two-inch diameter at PBNP). This difference would have no significant effect on the test data. The applicable test data is contained in Section 4.7 of the EPRI Safety And Relief Valve Test Report.
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WISCONSIN ELECTRIC PRELIMINARY EVALUATION POINT BEACli NUCLEAR PLANT Page 3 of 8 Test Conditions - the EPRI Test Program covers a range of fluid conditions chosen to effectively envelop those that must be considered for the PWR plants within the program. These include inlet fluid conditions of saturated steam, 150 degrees F water followed by saturated steam, saturated water, saturated steam followed by saturated water, subcooled (550 degrees F) water, and saturated steam followed by subcooled water. Backpressures to 650 psia have been used.
Preliminary review indicates that these testing conditions effectively envelop those which must be considered for PBNP.
3.2 Summary of Valve Test Results Safety Valves - the Crosby 6M6 and 3K6 safety valves generally operated successfully on saturated steam and saturated water, exhibiting rapid lift and stable behavior. In all cases they have functioned to relieve pressure and prevent excessive over-pressurization. Ilowever, during testing of valves with loop seals or with subcooled water at the valve inlet, valve chatter did occur on the test piping configuration. While this induced high-frequency pressure oscillations in the piping upstream of the valve, these oscillations did not appear to substantially affect either piping integrity or subsequent valve performance. Also, in some tests, full lift was delayed until the loop seal had cleared the valve. Again, subsequent valve performance did not appear to be substantially affected, and the valves functioned to relieve pressure and prevent overpressurization.
WISCONSIN FLECTRIC PRELIMINARY EVALUATION POINT BEACil NUCLEAR PLANT Page 4 of 8 Relief Valves - A Copes-Vulcan 17-4Pli relief valve was extensively teited at the Marshall and Wyle test facilities. Durinj the Marbsall test (steam only),
two sets of valve internals were utilized. While the valves did not always fully close, the maximum reported leakage was less than 0.8 gpm. At the Wyle facility, the valv3 was tested on both steam and water and the maxi aum reported leakage (for eight tests) was less than 0.08 gpm. These test results demonstrate the acceptability of the PBNP relief valves.
3.3 Conclusions The preliminary data reviewed to date indicate that the PBNP safety and relief valves will operate under expected NSSS operating and accident conditions.
Wisconsin Electric and EDS Nuclear are proceeding with the required detailed analyses. The results of this effort will be the subject of a future submittal.
g o a WISCONSIN ELECTRIC PRELIMINAFY EVALUATION POINT HEACll NUCLEAR PLANT Page 5 of 8 TABLE 1: SAFETY VALVE PARAMETERS, UNITS 1 AND 2 o Number of Valves (per unit) 2 o Manufacturer Crosby Valve and Gaje Co.
o Type Spring-loaded nozzle type relief valve o Designation: Size 4 K2 6 Style HB-BP-86 Type E Weight 520 lbs.
o Steam Flow Capacity 288,000 lbs./hr. (sat. steam)
(rated and maximum)
Inlet Outlet o Design Pressure and 2485 psig 500 psig Temperature 650 F 470 F o Valve Procurement Westinghouse G-676279, Specification (original) Specification 3.7.2, Rev. 1 l
e 9
WISCONSIN ELECTRIC PRELIMINARY EVALUATION POINT BEAf 11 NUCLEAR PLANT Page 6 of 8 TABLE 2: PELIEF AND BLOCK VALVE PARAMETERS, UNITS 1 AND 2 o Nunber of Valves (per unit) Relief: 2 Block: 2 o Mar uf acturer Relief: Copes-Vulcan Inc.
Block: Velan o Type Relief: Globe Valves Block: Gate Valves o Steam Flow (Relief Valves) 210,000 lbs ./hr . (max) 179,000 lbs./hr . (normal) o Design Pressure and 2485 psig/650 F Temperature (Relief and Block Valves) o Set Pressure (Relief Valves) 2335 psig
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4 WISCONSIN ELECTRIL PRELIMINARY EVALUATION POINT BEACH NUCLEAR PLANT Page 7 of 8 TABLE 3: SAFETY-RELATED SEISMICALLY-DESIGNED PRESSURIZER OUTI.ET PIPING, UNITS 1 AND 2 .
O Pressure and Operating Design Temperature
- Unit 1: 2235 psig/653 F 2485 psig/680*F Lines #RC-250lR-2
- RC-250lR-3
. - Unit 2: 2235 psig/653*F 2485 psig/680 F Lines #RC-250lR-2
- RC-250lR-3 i
o Piping Supports Numbers Type
! - Unit 1:
(Line #RC-250lR-2) HS-14 Snubber RC-14 Spring Hanger RC-15 Spring Hanger RC-16 Spring Hanger
- Unit 2:
4 (Line # RC-250lR-2) HS-28 Snubber (2)'
RC-15 Spring Hanger RC-13 Spring Hanger 2S-266 Rigid Hanger RC-14 Spring Hanger 1
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1 o .
WISCONSIN ELECTRIC PRELIMINARY EVALUATION i POINT BEAC NUCLEAR PLANT i
i Page 8 of 8 TABLE 4: pISCllARGE PIPING INFORMATION, UNITS 1 AND 2 o Pressure and Operating (max.) Design Temperature Unit 1:
(Lin: #RC-60lR-1) 497 psig/468*F 540 psig/477'F (Line #RC-60lR-2) 497 psig/468*F 540 psig/477*F Unit 2:
(Line #RC-601R-1) 497 psig/468* F 540 psig/ 477*F (Line # RC-60lR-2) 497 psig/468*F 540 psig/ 477 F o Piping Supports Number Type Unit 1:
(Line #SC-60lR-1) RS-200 Restraint HS-17 Snubber RC-17 Spring Hanger (Line #RC-60lR-2) HS-18 Snubber RC-12 Spring Hanger HS-200 Snubber S-248 Restraint RC-13 Spring Hanger H-200 Rigid Hanger RC-13A Spring Hanger RC-18 Spring Hanger S-247 Restraint Unit 2:
(Line #RC-60lR-1) H-201 Restraint HS-30 Snubber RC-10 Spring Hanger (Line # RC-60lR-2) HS-29 Snubber i RC.-ll Spring Hanger HS-1 Snubber 2S-265 Restraint RC-12 Spring Hanger H-200 Restraint .
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